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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ROSA-2 | CSNI2021/01 | Arrived | 15-MAY-2014 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| CSNI2021/01 | PC Windows |
The OECD/NEA ROSA-2 project aimed to resolve key light water reactor (LWR) thermal-hydraulics safety issues highlighted from the first phase of the project by using the ROSA/large-scale testing facility (LSTF) at the Japan Atomic Energy Agency.
In particular, the ROSA-2 Project focused on the validation of simulation models and methods for the following complex phenomena of high-safety relevance for thermal-hydraulic transients in design basis events (DBE) and beyond-DBE:
Generated a system-integral and a separate-effect experimental database to validate predictive capability and accuracy of computer codes and models. Thermal-hydraulic phenomena coupled with multi-dimensional flows that might have included mixing, stratification, counter-current flows, parallel-channel flows and oscillatory flows were the main focus of the investigations.
Facilitated assessment of codes in use for thermal-hydraulic safety analyses as well as advanced codes under development including three-dimensional computational fluid dynamics (CFD) codes through active involvement of the project partners who maintained and improved the technical competence in thermal-hydraulics for nuclear reactor safety (NRS) evaluations.
The experimental program was intended to provide a valuable and broadly usable database to achieve the above cited objectives. The OECD/NEA ROSA-2 Project consisted of six LSTF experiments that mainly included two groups of experiments which are intermediate break loss-of-coolant (LOCA) accidents and steam generator tube rupture (SGTR) accidents. One of the six experiments may have been directed to a different target following a discussion with the project partners.
Project period: 01 April 2009-31 March 2013.
Project participants
The project was supported by safety organisations, research laboratories and industry from the following countries: Belgium, the Czech Republic, Finland, France, Germany, Hungary, Japan, Republic of Korea, Spain, Sweden, Switzerland, the United Kingdom and the United States.
The distribution of this package is restricted to participating countries and subject to prior approval.
For more detailed information visit Nuclear Energy Agency (NEA) - Rig-of-safety Assessment (ROSA) Project
Keywords: LWR reactors, light-water reactors, safety assessment, thermal hydraulics.
